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Published 2003 | Version v1
Computer medium

Numerical simulation of liquid film around grid spacer with interface tracking method

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
  • 2. Yamato System Engineer, Hitachi, Ibaraki (Japan)

Description

Design studies of reduced-moderation water reactors (RMWR) are being carried out at JAERI as one candidate for the future reactors. The RMWR core adopts a hexagonal tight lattice arrangement with about 1 mm gap between adjacent fuel rods. To optimize the thermal design, the boiling transition (BT) in such a tight lattice core is one of most important subjects to be evaluated, but effects of the rod diameter, the rod gap and the spacer configuration have not been fully investigated. Thus, we made a plan to develop a mechanistic BT model to evaluate the geometry effects by a two-phase flow numerical simulation. In this paper, the results of TPFIT code with the advanced interface tracking method applied to the air-water two-phase flow simulations in rectangle duct are shown. (author)

Part of:
GENES4/ANP2003: International conference on global environment and advanced nuclear power plants

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
GENES4/ANP2003: International conference on global environment and advanced nuclear power plants
Imprint Pagination
[1675 p.]
Journal Page Range
[8 p.]

Conference

Title
International conference on global environment and advanced nuclear power plants
Acronym
GENES4/ANP2003
Dates
15-19 Sep 2003
Place
Kyoto (Japan)

INIS

Optional Information

Notes
This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Session 28. Boiling Transition, Paper 1111; 5 refs., 13 figs.